CA3070834C - Method for establishing the natural circulation of liquid metal coolant of a fast neutron nuclear chain reactor - Google Patents
Method for establishing the natural circulation of liquid metal coolant of a fast neutron nuclear chain reactor Download PDFInfo
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- CA3070834C CA3070834C CA3070834A CA3070834A CA3070834C CA 3070834 C CA3070834 C CA 3070834C CA 3070834 A CA3070834 A CA 3070834A CA 3070834 A CA3070834 A CA 3070834A CA 3070834 C CA3070834 C CA 3070834C
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- coolant
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- 239000002826 coolant Substances 0.000 title claims abstract description 49
- 229910001338 liquidmetal Inorganic materials 0.000 title claims abstract description 28
- 238000000034 method Methods 0.000 title claims description 15
- 238000005485 electric heating Methods 0.000 claims abstract description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical group C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 8
- 238000010438 heat treatment Methods 0.000 claims description 8
- 229910052708 sodium Inorganic materials 0.000 claims description 8
- 239000011734 sodium Substances 0.000 claims description 8
- 230000001133 acceleration Effects 0.000 claims description 3
- 230000005484 gravity Effects 0.000 claims description 3
- 244000126002 Ziziphus vulgaris Species 0.000 claims 1
- 238000001816 cooling Methods 0.000 claims 1
- 238000005086 pumping Methods 0.000 abstract description 3
- 230000007704 transition Effects 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 229910052786 argon Inorganic materials 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Other Liquid Machine Or Engine Such As Wave Power Use (AREA)
Abstract
The invention relates to the field of nuclear engineering and can be used to organize the natural circulation of liquid metal coolant in the heat sink of a fast neutron nuclear reactor. In order to create a driving pressure of circulation without using pumping equipment and to provide the required direction of natural circulation of the liquid metal coolant in the heat sink circuit of the fast neutron nuclear reactor in the absence of heat transfer ftom the reactor before filling the pipelines and equipment of the lifting and downing sections of the circuit, they are pre-heated by electric heating to temperatures T1 and T2, respectively, which are selected from the condition of inequality:
p1(7'1) g AH1 > p2(T2) g H2 + AP
p1(7'1) g AH1 > p2(T2) g H2 + AP
Description
METHOD FOR ESTABLISHING THE NATURAL CIRCULATION
OF LIQUID METAL COOLANT OF A FAST NEUTRON NUCLEAR
CHAIN REACTOR
Field The invention relates to the field of nuclear engineering and can be used to organize the natural circulation of liquid metal coolant in the heat sink of a fast neutron nuclear reactor.
Background The closest to this invention is a method of organizing the natural circulation of liquid metal coolant in the heat sink of a fast neutron nuclear reactor, comprising the pre-heating of the lift and down flow pipes and equipment of the heat sink circuit with their subsequent filling with heated coolant, starting the circulation of the coolant in the circuit and switching to the natural circulation mode (G.B. Usynin, E.V. Kusmartsev Fast neutron reactors: Textbook for universities / Edited by F.M. Mitenkova ¨ M,:
Energoatomizdat, 1985 p. 197).
The known method is as follows.
Pipelines and equipment for the lifting and downing sections of the heat sink circuit before the initial filling with liquid metal coolant (or after inspection and repair) have a temperature approximately equal to the ambient temperature. The liquid metal coolant located in the tank of the filling and drainage system is heated to a temperature of about 200-250 C. Therefore, before supplying the heated liquid metal coolant to the heat sink circuit, the pipelines and equipment must be heated to the same temperature to prevent overcooling ("hardening") of the liquid metal coolant. For heating, electric heaters are used, which are installed on pipelines and equipment of the lifting and downing sections of the heat sink circuit. Then, the heated coolant is fed into the heat sink circuit until the required level in the tank for compensating thermal expansions is reached. After filling the lifting and downing sections Date Recue/Date Received 2021-03-15 of the circuit with the coolant, the forced circulation is started in the circuit using pumps. The transition to the natural circulation mode is made after the nuclear reactor reaches its rated operating parameters.
The disadvantage of this method is the presence of additional hydraulic 35 resistance in the circuit due to the pumping equipment used when starting the circulation and in the forced circulation mode until the reactor reaches its rated power, as well as the inability to switch from the forced circulation mode to natural circulation without heat transfer from the nuclear reactor.
40 Brief Description of Drawings Figure 1 is a diagram of the heat sink circuit of a fast neutron nuclear reactor.
Figure 2 is a graph of the natural circulation development without using a pump.
Description The objective of this invention is to provide a method for organizing the natural circulation of liquid metal coolant in the heat sink circuit of a fast neutron nuclear reactor, in which there is no forced circulation mode, and the heat sink circuit works, including when starting, only in the natural circulation mode and in the absence of heat transfer from the nuclear reactor, i.e. before power ascension, which ensures the passive safety of the nuclear reactor and the reactor unit as a whole.
The technical result of this invention is to initiate natural circulation by creating a driving pressure of circulation and providing the desired direction of natural circulation of the liquid metal coolant in the heat sink without transferring heat from the nuclear reactor. In addition, the technical result is a significant reduction in hydraulic resistance due to the lack of pumping equipment in the heat sink circuit.
OF LIQUID METAL COOLANT OF A FAST NEUTRON NUCLEAR
CHAIN REACTOR
Field The invention relates to the field of nuclear engineering and can be used to organize the natural circulation of liquid metal coolant in the heat sink of a fast neutron nuclear reactor.
Background The closest to this invention is a method of organizing the natural circulation of liquid metal coolant in the heat sink of a fast neutron nuclear reactor, comprising the pre-heating of the lift and down flow pipes and equipment of the heat sink circuit with their subsequent filling with heated coolant, starting the circulation of the coolant in the circuit and switching to the natural circulation mode (G.B. Usynin, E.V. Kusmartsev Fast neutron reactors: Textbook for universities / Edited by F.M. Mitenkova ¨ M,:
Energoatomizdat, 1985 p. 197).
The known method is as follows.
Pipelines and equipment for the lifting and downing sections of the heat sink circuit before the initial filling with liquid metal coolant (or after inspection and repair) have a temperature approximately equal to the ambient temperature. The liquid metal coolant located in the tank of the filling and drainage system is heated to a temperature of about 200-250 C. Therefore, before supplying the heated liquid metal coolant to the heat sink circuit, the pipelines and equipment must be heated to the same temperature to prevent overcooling ("hardening") of the liquid metal coolant. For heating, electric heaters are used, which are installed on pipelines and equipment of the lifting and downing sections of the heat sink circuit. Then, the heated coolant is fed into the heat sink circuit until the required level in the tank for compensating thermal expansions is reached. After filling the lifting and downing sections Date Recue/Date Received 2021-03-15 of the circuit with the coolant, the forced circulation is started in the circuit using pumps. The transition to the natural circulation mode is made after the nuclear reactor reaches its rated operating parameters.
The disadvantage of this method is the presence of additional hydraulic 35 resistance in the circuit due to the pumping equipment used when starting the circulation and in the forced circulation mode until the reactor reaches its rated power, as well as the inability to switch from the forced circulation mode to natural circulation without heat transfer from the nuclear reactor.
40 Brief Description of Drawings Figure 1 is a diagram of the heat sink circuit of a fast neutron nuclear reactor.
Figure 2 is a graph of the natural circulation development without using a pump.
Description The objective of this invention is to provide a method for organizing the natural circulation of liquid metal coolant in the heat sink circuit of a fast neutron nuclear reactor, in which there is no forced circulation mode, and the heat sink circuit works, including when starting, only in the natural circulation mode and in the absence of heat transfer from the nuclear reactor, i.e. before power ascension, which ensures the passive safety of the nuclear reactor and the reactor unit as a whole.
The technical result of this invention is to initiate natural circulation by creating a driving pressure of circulation and providing the desired direction of natural circulation of the liquid metal coolant in the heat sink without transferring heat from the nuclear reactor. In addition, the technical result is a significant reduction in hydraulic resistance due to the lack of pumping equipment in the heat sink circuit.
2 Date Recue/Date Received 2020-06-03 60 The specified technical result is achieved by method of organizing the natural circulation of a liquid metal coolant in the heat sink of the fast neutron nuclear reactor, which includes the preliminary electric heating of pipelines and equipment of the lifting and downing sections of the heat sink, followed by their filling with a heated coolant, starting the circulation of the coolant in 65 the circuit and transition to the natural circulation mode. According to an embodiment, pipelines and equipment of the lifting and downing sections of the heat sink circuit are pre-heated to temperatures T1 and T2, respectively, which are selected from the conditions of inequality:
NM) g 21H1> p2(T2) g 11H2 + ZIP, 70 where:
pi(Ti) is the density of the liquid metal coolant at temperature T1 of pipelines and equipment in the lifting section;
p2(T2) is the density of the liquid metal coolant at temperature T2 of pipelines and equipment at the downing section;
75 Hi is the height difference between the inlet and outlet of the lifting section;
AH2 is the height difference between the inlet and outlet of the downing section;
AP is the hydraulic resistance of the circuit SO g is the acceleration of gravity, and the circulation of the coolant in the circuit is launched simultaneously with the transition to the natural circulation mode and until the nuclear reactor reaches its nominal operating parameters due to the difference in densities pi(Ti) and p2(T2) of the liquid metal coolant, respectively, in the lifting and 85 downing sections of the circuit.
Features allow the natural circulation to start in the heat sink of the nuclear reactor without connecting to the main heat source, but only due to electric heating to the calculated temperature of the pipelines and equipment of the lifting and downing sections and, therefore, due to the temperature
NM) g 21H1> p2(T2) g 11H2 + ZIP, 70 where:
pi(Ti) is the density of the liquid metal coolant at temperature T1 of pipelines and equipment in the lifting section;
p2(T2) is the density of the liquid metal coolant at temperature T2 of pipelines and equipment at the downing section;
75 Hi is the height difference between the inlet and outlet of the lifting section;
AH2 is the height difference between the inlet and outlet of the downing section;
AP is the hydraulic resistance of the circuit SO g is the acceleration of gravity, and the circulation of the coolant in the circuit is launched simultaneously with the transition to the natural circulation mode and until the nuclear reactor reaches its nominal operating parameters due to the difference in densities pi(Ti) and p2(T2) of the liquid metal coolant, respectively, in the lifting and 85 downing sections of the circuit.
Features allow the natural circulation to start in the heat sink of the nuclear reactor without connecting to the main heat source, but only due to electric heating to the calculated temperature of the pipelines and equipment of the lifting and downing sections and, therefore, due to the temperature
3 Date Recue/Date Received 2020-10-29 90 difference (density difference) of the coolant filling them. Therefore, at the time of the nuclear reactor starting, the heat sink circuit will already function in the natural circulation mode and thereby ensure the passive safety of the reactor unit as a whole. Compared to the prototype, there is no forced circulation mode, which also helps increase nuclear safety.
95 An embodiment of this invention is illustrated by drawings, where a diagram of a heat sink circuit of the fast neutron nuclear reactor is presented in the Figure 1, and Figure 2 shows a graph of the development of natural circulation without using a pump.
The heat sink circuit contains heat source 1, which can be used as a heat 100 exchanger that is connected to the first reactor circuit (not shown in the drawing) or a nuclear reactor (not shown in the drawing). The output of heat source 1 is connected by means of a lifting pipe 2 with the input of the device for removing heat 3, which is used as an air heat exchanger. Sectional electric heaters 4 are installed on the lifting pipe 2 along the entire length. The outlet 105 of heat removal device 3 is connected by downing pipe 5 to heat source through a tank to compensate thermal expansion of coolant 6. Sectional electric heaters 7, similar to electric heaters 4, are installed on downing pipe 5 along the entire length. The heat sink circuit is connected to the tank of filling and drainage system 8 by means of drainage pipe 9 with valve 10. Heat 110 source 1, heat removal device 3 and tank for compensating thermal expansion of the coolant 6 are equipped with sectioned electric heaters (not shown in the drawing). To minimize heat loss, the heat sink circuit (pipelines 2, 5, 9, heat source 1, heat removal device 3 and tank for compensating thermal expansion of the coolant 6) is provided with thermal insulation (not shown in the 115 drawing).
In an embodiment, the method is as follows.
To organize the natural circulation of the liquid metal coolant, which is preferably sodium, the following sequence of actions is performed in the heat
95 An embodiment of this invention is illustrated by drawings, where a diagram of a heat sink circuit of the fast neutron nuclear reactor is presented in the Figure 1, and Figure 2 shows a graph of the development of natural circulation without using a pump.
The heat sink circuit contains heat source 1, which can be used as a heat 100 exchanger that is connected to the first reactor circuit (not shown in the drawing) or a nuclear reactor (not shown in the drawing). The output of heat source 1 is connected by means of a lifting pipe 2 with the input of the device for removing heat 3, which is used as an air heat exchanger. Sectional electric heaters 4 are installed on the lifting pipe 2 along the entire length. The outlet 105 of heat removal device 3 is connected by downing pipe 5 to heat source through a tank to compensate thermal expansion of coolant 6. Sectional electric heaters 7, similar to electric heaters 4, are installed on downing pipe 5 along the entire length. The heat sink circuit is connected to the tank of filling and drainage system 8 by means of drainage pipe 9 with valve 10. Heat 110 source 1, heat removal device 3 and tank for compensating thermal expansion of the coolant 6 are equipped with sectioned electric heaters (not shown in the drawing). To minimize heat loss, the heat sink circuit (pipelines 2, 5, 9, heat source 1, heat removal device 3 and tank for compensating thermal expansion of the coolant 6) is provided with thermal insulation (not shown in the 115 drawing).
In an embodiment, the method is as follows.
To organize the natural circulation of the liquid metal coolant, which is preferably sodium, the following sequence of actions is performed in the heat
4 Date Recue/Date Received 2020-10-29 120 sink circuit of the research fast neutron nuclear reactor.
Sectionalized electric heaters 4 and 7 are switched on for heating pipelines and equipment for the lifting and downing sections of the heat sink circuit to the calculated temperatures T1 = 230 C and T2 = 210 C, respectively. At the same time, the settings of the current regulators provide heating and maintaining the 125 temperature for heat source 1 - 230 C, for the lifting pipe 2 - 230 C, for the heat removal device 3 - 210 C, for downing pipe 5 and the tank for compensating thermal expansion of coolant 6 - 210 C. Then, evacuation and argon filling of the heat sink circuit are successively performed, and after reaching the required composition of the heat sink circuit gaseous medium, 130 sodium is supplied to the heat sink circuit through the drainage pipe 9 with a flow rate of 2 m3/h and temperature of 225 C from the tank of the filling and drainage system 8, by opening the valve 10. In start-up mode, the heat source 1 does not work as a heat exchanger, but is used only for the passage of the coolant through it. When sodium reaches the required level in the tank for 135 compensating thermal expansion 6, valve 10 is closed. The pressure in the gas cavity of tank for compensating thermal expansion 6 rises to 0.14 MPa. In the process of filling the heat sink circuit, the sodium coolant receives the temperature of the pipelines walls and the equipment of the circuit, as a result of which a driving pressure of natural circulation is created in the desired 140 direction. As shown in Fig. 2 under the influence of the natural circulation pressure created by the initial temperature difference T1 and T2 of the walls of lifting pipeline 2 and lowering pipeline 5, the sodium flow rate increases from zero to a stabilized value of 3.76 kg/s for 150 s and then remains constant.
In the steady state of natural circulation, heat removal device 3 provides the 145 necessary reduction in the temperature of the coolant at the entrance of the downing section. The temperature of sodium at the inlet and outlet of the circuit elements is 210 C at the input of the heat source 1, 225 C at the output of heat source 1, 230 C at the input of heat removal device 3, 210 C
at the output of heat removal device 3. To calculate the temperatures T1 and Date Recue/Date Received 2020-06-03 150 12, the following values were used: the height of heat source output 1 ¨ 6.2 the height of heat removal device input 3 ¨ 11.1 m, the height of heat removal device output 3 - 8.4 m, the height of heat source input 1 ¨ 6.9 m, coolant density on the lifting section pi(Ti) ¨ 896 kg/m3, the density of the coolant in the downing section p2(T2) ¨ 901 kg/m3, the height difference 155 between the inlet and outlet of the lifting section AH1 ¨ 4.9 m, the height difference between the inlet and outlet of the downing section AI-12 ¨ 1.5 in, the hydraulic resistance of the circuit ¨ 1,600 Pa.
Date Recue/Date Received 2020-06-03
Sectionalized electric heaters 4 and 7 are switched on for heating pipelines and equipment for the lifting and downing sections of the heat sink circuit to the calculated temperatures T1 = 230 C and T2 = 210 C, respectively. At the same time, the settings of the current regulators provide heating and maintaining the 125 temperature for heat source 1 - 230 C, for the lifting pipe 2 - 230 C, for the heat removal device 3 - 210 C, for downing pipe 5 and the tank for compensating thermal expansion of coolant 6 - 210 C. Then, evacuation and argon filling of the heat sink circuit are successively performed, and after reaching the required composition of the heat sink circuit gaseous medium, 130 sodium is supplied to the heat sink circuit through the drainage pipe 9 with a flow rate of 2 m3/h and temperature of 225 C from the tank of the filling and drainage system 8, by opening the valve 10. In start-up mode, the heat source 1 does not work as a heat exchanger, but is used only for the passage of the coolant through it. When sodium reaches the required level in the tank for 135 compensating thermal expansion 6, valve 10 is closed. The pressure in the gas cavity of tank for compensating thermal expansion 6 rises to 0.14 MPa. In the process of filling the heat sink circuit, the sodium coolant receives the temperature of the pipelines walls and the equipment of the circuit, as a result of which a driving pressure of natural circulation is created in the desired 140 direction. As shown in Fig. 2 under the influence of the natural circulation pressure created by the initial temperature difference T1 and T2 of the walls of lifting pipeline 2 and lowering pipeline 5, the sodium flow rate increases from zero to a stabilized value of 3.76 kg/s for 150 s and then remains constant.
In the steady state of natural circulation, heat removal device 3 provides the 145 necessary reduction in the temperature of the coolant at the entrance of the downing section. The temperature of sodium at the inlet and outlet of the circuit elements is 210 C at the input of the heat source 1, 225 C at the output of heat source 1, 230 C at the input of heat removal device 3, 210 C
at the output of heat removal device 3. To calculate the temperatures T1 and Date Recue/Date Received 2020-06-03 150 12, the following values were used: the height of heat source output 1 ¨ 6.2 the height of heat removal device input 3 ¨ 11.1 m, the height of heat removal device output 3 - 8.4 m, the height of heat source input 1 ¨ 6.9 m, coolant density on the lifting section pi(Ti) ¨ 896 kg/m3, the density of the coolant in the downing section p2(T2) ¨ 901 kg/m3, the height difference 155 between the inlet and outlet of the lifting section AH1 ¨ 4.9 m, the height difference between the inlet and outlet of the downing section AI-12 ¨ 1.5 in, the hydraulic resistance of the circuit ¨ 1,600 Pa.
Date Recue/Date Received 2020-06-03
Claims (11)
1. A method for launching a natural circulation of a liquid metal coolant in a heat sink circuit of a fast neutron nuclear reactor, the heat sink circuit comprising pipelines and equipment of both a lifting section and a downing section, the method comprising pre-heating the pipelines and equipment of the lifting and the downing section of the heat sink circuit;
filling the pipelines and equipment with heated coolant;
causing a circulation of the heated coolant in the heat sink circuit;
switching to the natural circulation mode, wherein the pipelines and equipment of the lifting section and the downing section of the heat sink circuit are pre-heated by electric heating respectively, to temperatures Ti and T2, which are selected from the conditions of inequality:
p1(T1) g AII1> p2(T2) g ii112+ iiP
where:
pi(Ti) is a density of the liquid metal coolant at temperature T1 of pipelines and equipment in the lifting section;
p2(T2) is a density of the liquid metal coolant at temperature T2 of pipelines and equipment at the downing section;
Atli is a height difference between an inlet and an outlet of the lifting section;
412 is a height difference between an inlet and an outlet of the downing section;
P is a hydraulic resistance of the circuit;
g is the acceleration of gravity, simultaneously launching of circulation of the coolant in the heat sink circuit with the switching to the natural circulation mode until the liquid metal coolant in the fast neutron nuclear reactor is circulating due to a difference in densities pi(Ti) and p2(T2) of the liquid metal coolant, respectively, in the lifting section and downing section of the circuit.
filling the pipelines and equipment with heated coolant;
causing a circulation of the heated coolant in the heat sink circuit;
switching to the natural circulation mode, wherein the pipelines and equipment of the lifting section and the downing section of the heat sink circuit are pre-heated by electric heating respectively, to temperatures Ti and T2, which are selected from the conditions of inequality:
p1(T1) g AII1> p2(T2) g ii112+ iiP
where:
pi(Ti) is a density of the liquid metal coolant at temperature T1 of pipelines and equipment in the lifting section;
p2(T2) is a density of the liquid metal coolant at temperature T2 of pipelines and equipment at the downing section;
Atli is a height difference between an inlet and an outlet of the lifting section;
412 is a height difference between an inlet and an outlet of the downing section;
P is a hydraulic resistance of the circuit;
g is the acceleration of gravity, simultaneously launching of circulation of the coolant in the heat sink circuit with the switching to the natural circulation mode until the liquid metal coolant in the fast neutron nuclear reactor is circulating due to a difference in densities pi(Ti) and p2(T2) of the liquid metal coolant, respectively, in the lifting section and downing section of the circuit.
2. The method of claim 1 wherein the liquid metal coolant is sodium.
3. The method of claim 3 wherein Ti is 230 C and T2 is 210 C.
Date Recue/Date Received 2021-04-21
Date Recue/Date Received 2021-04-21
4. The method of claims 2 or 3 wherein the filling the pipelines and equipment with heated coolant is performed at a flow rate of 2 m3/hr and a temperature of 225 C.
5. The method of any one of claims 1 to 4 wherein the pre-heating of the pipelines and equipment is performed by sectional electric heaters.
6. A system for cooling a fast neutron nuclear reactor, the system comprising:
a heat sink circuit in communication with a heat source of the nuclear reactor, wherein the heat sink circuit includes a lifting section and a downing section;
the lifting section of the heat sink circuit configured with one or more electric preliminary lifting section heating elements, in communication with the heat source and an air heat exchanger;
the downing section of the heat sink circuit configured with one or more electric preliminary downing section heating elements, in communication with the air heat exchanger and the heat source, wherein a thermal expansion tank is configured in the downing section between the air heat exchanger and the heat source;
a tank for drainage in communication with the lifting section including a valve;
wherein a temperature of the liquid metal coolant in the lifting section is Ti and wherein a temperature of the liquid metal coolant in the downing section is T2, selected from conditions of inequality, pi(Ti) gH1 > P2(T2)* AH2+ AP
wherein pi(Ti) is a density of the liquid metal coolant at temperature Ti in the lifting section;
wherein p2(T2) is a density of the liquid metal coolant at temperature T2 in the downing section;
wherein A111 is a height between a lifting section inlet at a top of the air heat exchanger and a lifting section outlet at a bottom of the heat source;
Date Recue/Date Received 2021-04-21 wherein ii}12 is a height between a downing section outlet at a bottom of the air heat exchanger and a downing section inlet at a top of the heat source;
wherein P is a hydraulic resistance of the circuit;
wherein g is the acceleration of gravity.
a heat sink circuit in communication with a heat source of the nuclear reactor, wherein the heat sink circuit includes a lifting section and a downing section;
the lifting section of the heat sink circuit configured with one or more electric preliminary lifting section heating elements, in communication with the heat source and an air heat exchanger;
the downing section of the heat sink circuit configured with one or more electric preliminary downing section heating elements, in communication with the air heat exchanger and the heat source, wherein a thermal expansion tank is configured in the downing section between the air heat exchanger and the heat source;
a tank for drainage in communication with the lifting section including a valve;
wherein a temperature of the liquid metal coolant in the lifting section is Ti and wherein a temperature of the liquid metal coolant in the downing section is T2, selected from conditions of inequality, pi(Ti) gH1 > P2(T2)* AH2+ AP
wherein pi(Ti) is a density of the liquid metal coolant at temperature Ti in the lifting section;
wherein p2(T2) is a density of the liquid metal coolant at temperature T2 in the downing section;
wherein A111 is a height between a lifting section inlet at a top of the air heat exchanger and a lifting section outlet at a bottom of the heat source;
Date Recue/Date Received 2021-04-21 wherein ii}12 is a height between a downing section outlet at a bottom of the air heat exchanger and a downing section inlet at a top of the heat source;
wherein P is a hydraulic resistance of the circuit;
wherein g is the acceleration of gravity.
7. The system of claim 6 wherein the liquid metal coolant is sodium.
8. The system of claim 7 wherein Ti is 230 C and T2 is 210 C.
io 9. The system of any one of claims 6 to 8, wherein a pressure of gas in the thermal expansion tank is 0.14 MPa during operation.
10. The system of any one of claims 6 to 9, wherein a height of the lifting section outlet at the bottom of the heat source is 6.2 meters, a height of the lifting section inlet at the top of the air heat exchanger is 11.1 meters, a height of the downing section outlet at the bottom of the air heat exchanger is 8.4 meters and a height of the downing section inlet at the top of the heat source is 6.9 meters.
11. The system of any one of claims 6 to 10, wherein111-11 is 4.9 meters and 111-12 is 1.5 meters.
Date Recue/Date Received 2021-04-21
Date Recue/Date Received 2021-04-21
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| RU2017126521A RU2691755C2 (en) | 2017-07-24 | 2017-07-24 | Method of natural circulation of a liquid metal coolant of a fast neutron reactor |
| RU2017126521 | 2017-07-24 | ||
| PCT/RU2018/000478 WO2019022640A1 (en) | 2017-07-24 | 2018-07-18 | Method of establishing natural circulation of a liquid metal coolant in a fast neutron reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CA3070834A1 CA3070834A1 (en) | 2019-01-31 |
| CA3070834C true CA3070834C (en) | 2021-08-31 |
Family
ID=65037248
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA3070834A Active CA3070834C (en) | 2017-07-24 | 2018-07-18 | Method for establishing the natural circulation of liquid metal coolant of a fast neutron nuclear chain reactor |
Country Status (12)
| Country | Link |
|---|---|
| US (1) | US10937558B2 (en) |
| EP (1) | EP3660862B1 (en) |
| JP (1) | JP6930797B2 (en) |
| KR (1) | KR102188486B1 (en) |
| CN (1) | CN110959182B (en) |
| AU (1) | AU2018308297A1 (en) |
| CA (1) | CA3070834C (en) |
| HU (1) | HUE055875T2 (en) |
| PL (1) | PL3660862T3 (en) |
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| CN111524619B (en) * | 2020-06-19 | 2022-06-07 | 中国核动力研究设计院 | Experimental device and method for researching dynamic self-feedback characteristic of natural circulation system |
| CN111951987B (en) * | 2020-09-04 | 2022-07-29 | 东南大学 | Small modular reactor coolant system and experimental method applying same |
| RU2762391C1 (en) * | 2021-06-27 | 2021-12-20 | Виталий Алексеевич Узиков | Fast neutron reactor with a passive core cooling system |
Family Cites Families (18)
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|---|---|---|---|---|
| FR2451616A2 (en) * | 1979-02-09 | 1980-10-10 | Electricite De France | IMPROVEMENTS ON SECONDARY HEATER CIRCUITS FOR NUCLEAR REACTORS COOLED BY LIQUID SODIUM |
| GB2076618B (en) * | 1980-05-23 | 1984-02-01 | Daido Ind | Preheater for mounting in a well tube |
| JPS5786090A (en) | 1980-11-17 | 1982-05-28 | Tokyo Shibaura Electric Co | Auxiliary core cooling device |
| JPS6029225U (en) | 1983-08-03 | 1985-02-27 | 株式会社日立製作所 | Overflow pipe preheating device |
| JPS6120893A (en) | 1984-07-06 | 1986-01-29 | 株式会社東芝 | Cooling device for liquid metal |
| US5021211A (en) * | 1989-07-25 | 1991-06-04 | General Electric Company | Liquid metal cooled nuclear reactors with passive cooling system |
| US5202083A (en) * | 1992-02-28 | 1993-04-13 | Atomic Energy Of Canada Limited | Passive shutdown cooling system for nuclear reactors |
| RU2188472C2 (en) * | 2000-11-08 | 2002-08-27 | Опытное Конструкторское Бюро "Гидропресс" | Method for transferring heat energy of source to working medium of power installation with aid of liquid-metal coolant |
| JP2003262690A (en) | 2002-03-11 | 2003-09-19 | Mitsubishi Heavy Ind Ltd | Decay heat removal system |
| RU2212066C1 (en) * | 2002-05-17 | 2003-09-10 | Фгуп Окб "Гидропресс" | Steam-generating nuclear reactor unit using liquid-metal coolant |
| KR100597722B1 (en) * | 2004-01-02 | 2006-07-10 | 한국원자력연구소 | Stable and passive decay heat removal system for liquid metal reator |
| US8891723B2 (en) * | 2007-11-15 | 2014-11-18 | State of Oregon Acting by and Through The State Board of Higher Education on Behalf or Oregon State University, The Oregon State University | Stable startup system for a nuclear reactor |
| JP5624355B2 (en) | 2010-04-21 | 2014-11-12 | 株式会社東芝 | Liquid metal cooled nuclear reactor and heat removal method thereof |
| CN103021483B (en) | 2012-12-31 | 2015-08-19 | 中国科学院合肥物质科学研究院 | A kind of auxiliary heating system for liquid metal cooling natural circulation reactor |
| CN103366838B (en) | 2013-07-17 | 2015-08-12 | 中国科学院上海应用物理研究所 | A kind of MSR buffer salt natural circulation cooling system |
| RU2545098C1 (en) | 2014-01-31 | 2015-03-27 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Reactor plant with fast neutron reactor and lead coolant |
| CN105551551B (en) | 2015-12-17 | 2018-04-20 | 中国原子能科学研究院 | A kind of pool type natrium cold fast reactor low power run method that conventional island input is not required |
| CN106409353B (en) | 2016-09-26 | 2018-09-07 | 南华大学 | It is a kind of based on gaslift liquid metal cooling the multi-functional heap of pool reactor in hot separating system |
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| HUE055875T2 (en) | 2021-12-28 |
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| PL3660862T3 (en) | 2021-12-27 |
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| EP3660862A4 (en) | 2020-07-01 |
| RU2017126521A (en) | 2019-01-24 |
| RU2017126521A3 (en) | 2019-01-24 |
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| CA3070834A1 (en) | 2019-01-31 |
| KR20200030553A (en) | 2020-03-20 |
| US20200161008A1 (en) | 2020-05-21 |
| WO2019022640A1 (en) | 2019-01-31 |
| CN110959182B (en) | 2021-05-04 |
| RU2691755C2 (en) | 2019-06-18 |
| BR112020001519A2 (en) | 2020-09-08 |
| EP3660862B1 (en) | 2021-07-07 |
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